Nucleonic analysis of a preliminary design for the ETF neutral-beam-injector duct shielding
Conference
·
OSTI ID:7072474
A nucleonic analysis of the Engineering Test Facility Neutral-Beam-Injector duct shielding has been made using a hybrid Monte Carlo/discrete-ordinates method. This method used Monte Carlo to determine internal and external boundary surface sources for a subsequent discrete-ordinates calculation of the neutron and gamma-ray transport through the shield. The analysis also included determination of the energy and angular distribution of neutrons and gamma rays entering the duct from the torus plasma chamber. Confidence in the hybrid method and the results obtained were provided through a comparison with three-dimensional Monte Carlo results.
- Research Organization:
- Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 7072474
- Report Number(s):
- LA-UR-80-2926; CONF-801011-59; TRN: 80-019717
- Resource Relation:
- Conference: 4. ANS topical meeting on the technology of controlled nuclear fusion, King of Prussia, PA, USA, 14 Oct 1980
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
NEUTRAL BEAM SOURCES
NEUTRON TRANSPORT
TOKAMAK ETF
BEAM TRANSPORT
DISCRETE ORDINATE METHOD
GAMMA RADIATION
MONTE CARLO METHOD
SHIELDING
ELECTROMAGNETIC RADIATION
IONIZING RADIATIONS
NEUTRAL-PARTICLE TRANSPORT
RADIATION TRANSPORT
RADIATIONS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700205* - Fusion Power Plant Technology- Fuel
Heating
& Injection Systems
NEUTRAL BEAM SOURCES
NEUTRON TRANSPORT
TOKAMAK ETF
BEAM TRANSPORT
DISCRETE ORDINATE METHOD
GAMMA RADIATION
MONTE CARLO METHOD
SHIELDING
ELECTROMAGNETIC RADIATION
IONIZING RADIATIONS
NEUTRAL-PARTICLE TRANSPORT
RADIATION TRANSPORT
RADIATIONS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700205* - Fusion Power Plant Technology- Fuel
Heating
& Injection Systems